ML20126H989

Proposed Tech Specs Revising Fire Pump Diesel Engine Surveillance Requirement,Correcting RCS Vol & Identifying Low Population Zone

ML20126H989
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	06/14/1985
From:	PORTLAND GENERAL ELECTRIC CO.
To:
Shared Package
ML20126H974	List: ML20126H969 ML20126H980 ML20126H989
References
NUDOCS 8506180494
Download: ML20126H989 (5)

Text

LCA 122

.. Attachment 1 Page 1 of 4 3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 BORATION CONTROL 3/4.1.1.1 SHUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that 1) the reactor can be made subcritical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and 3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.

SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS Tavg. The most restrictive condition occurs at EOL, with Tavg at no load operating temperature, and is associated with postulated steam line break accident and resulting uncontrolled RCS cooldown. In the analysis of this accident, a minimum SHUTDOWN MARGIN of 1.6% Ak/k is initially required to control the reactivity transient. Accordingly, the SHUTDOWN MARGIN requirement is based upon this limiting condition and is consistent with FSAR accident analysis assumptions. With Tavg less than 200*F, the most restrictive reactivity transients resulting from the postulated Boron Dilution Accident are such that a 1.6% Ak/k SHUTDOWN MARGIN is initially required.

3/4.1.1.3 BORON DILUTION A minimum flow rate of at least 3000 GPM provides adequate mixing, prevents stratification and ensures that reactivity changes will be gradual during boron concentration reductions in the Reactor Coolant System. A flow rate of at least 3000 GPM will circulate an equivalent Reactor Coolant System volume of 12,900 cubic feet in approximately 33 minutes. The l reactivity change rate associated with boron reductions will therefore be within the capability for operator recognition and control.

3/4.1.1.4 MODERATOR TEMPERATURE COEFFICIENT (MTC) 1 The limitations on MTC are provided to ensure that the assumptions used in the accident and transient analyses remain valid through each fuel cycle. The surveillance requirement for measurement of the MTC at the beginning,' middle, and near the end of each fuel cycle is adequate to confirm the MTC value since this coefficient changes slowly due l

l TROJAN-UNIT 1 B 3/4 1-1 Amendment No. Ed 8506180494 IB50614 PDR ADOCK 05000344 P PDR l

1 LCA 122 Attachment 1 Pane 2 of 4 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

f. At least once per 3 years by performing a flow test of the system in accordance with Chapter 5, Section 11 of the Fire Protection Handbook, 14th Edition, published by the National Fire Protection Association.

4.7.8.1.2 The fire pump diesel engine shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying:

1. The fuel storage tank contains at least 200 gallons of fuel, and

2. The diesel starts from ambient conditions and operates for at least 20 minutes.

b. At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank, obtained in accord-ance with ASTM-D270-65, is within the acceptable limits specified in Table 1 of ASTM D975-78 when checked for water, viscosity and sediment.

c. At least once per 18 months by subjecting the diesel to l an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for the class of service.

4.7.8.1.3 The fire pump diesel starting 24-volt battery bank and charger shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that:

1. The electrolyte level of each battery is above the plates, and

2. The overall battery voltage is >24 volts.

TROJAN-UNIT 1 3/4 7-25 Amendment No. 73, 39, IG A -. . - _.. -. __ __. _ . _ _ ____ __

- LCA 122 Attachment 1 TROJAN NUCLEAR PLANT Page 3 of 4 LOW POPULATION ZONE 2.5 Mile Radius

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LCA 122 2 . .,

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l DESIGN FEATURES a.- In accordance with the code requirements specified in Section

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5.2 of the FSAR, with allowance for normal degradation pursuant to the applicable' Surveillance Requirements,

b. For a pressure. of_ 2485 psig, and

.c. For a' temperature of '650*F, except for the pressurizer which is 680*F.

-VOLUME 5.4.2 - The total water and steam volume of the Reactor Coolant System is 12,900 i 100 cubic feet-at a nominal Tavg of 584.7'F. l 5.5- ENER6ENCY CORE COOLING-SYSTEMS

. 5.5.1 - The emergency core cooling systems are designed and shall be maintained in accordance with the original design provisions contained in Section'6'.3 of the FSAR with allowance for normal degradation pursuant to the_ applicable Surveillance Requirements.

5.6 FUEL STORAGE CRITICALITY 5.6.1.1 -The fuel storage racks for new fuel are designed and shall be maintained with a nominal 21-inch center-to-center distance between fuel assemblies placed in the storage racks to ensure a Keff of 50.95 with the storage pit filled with unborated water,' and with new fuel containing not more than 44.3 grams of U-235 per axial. centimeter of active fuel assembly (3.5 wt5 enrichment). The criticality analysis includes a conservative allowance for uncertainties as described in Section 4.3.2.7 of the FSAR, as amended through Amendment 26.

. 5.6.1.2 The storage racks for spent fuel are designed and shall be main-tained with a nominal 10.5-inch center-to-center distance between fuel L assemblies' placed in the storage racks to ensure a Keyy 'of $0.95 with the storage pool filled with unborated water and with new fuel containing not more than 57.0 grams of U-235 per axial centimeter of active fuel assembly (4.5 wt5 enrichment)'. The criticality analysis includes a con-servative allowance for uncertainties as described in Section 3.1 of -

PGE-1037.

TROJAN-UNIT.l' 5-5 Amendment No. 25,'3#, di u

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UNITED STATES OF AMERICA  ;

NUCLEAR REGULATORY COMMISSION '

l In the Matter of )

)

PORTLAND GENERAL ELECTRIC COMPANY, ) Docket 50-344 THE CITY OF EUGENE, OREGON, AND ) Operating License NPF-1 PACIFIC POWER & LIGHT COMPANY )

)

(TROJAN NUCLEAR PLANT) )

CERTIFICATE OF SERVICE I hereby certify that copies of License Change Application 122 to the Operating License for Trojan Nuclear Plant, dated June 14, 1985, have been served on the following by hand delivery or by deposit in the United States mail, first class, this 14th day of June 1985:

Mr. Lynn Frank, Director State of Oregon Department of Energy Labor & Industries Bldg. Rm 102 Salem OR 97310 Mr. Robert M. Hunt Chairman of County Commissioners Columbia County Courthouse St. Helens OR 97051 l /t G. Zimmerman, Manager Nuc ar Regulation Branch

( Nucl r Safety & Regulation i

l Subscribed and sworn to before me this 14th day of June 1985.

MAlJA Notary Public of gp6gon My Commission Expires: .

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